JPS6010594B2 - nuclear power plant - Google Patents

nuclear power plant

Info

Publication number
JPS6010594B2
JPS6010594B2 JP52007019A JP701977A JPS6010594B2 JP S6010594 B2 JPS6010594 B2 JP S6010594B2 JP 52007019 A JP52007019 A JP 52007019A JP 701977 A JP701977 A JP 701977A JP S6010594 B2 JPS6010594 B2 JP S6010594B2
Authority
JP
Japan
Prior art keywords
water
turbine
main
pump
steam
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
JP52007019A
Other languages
Japanese (ja)
Other versions
JPS5392100A (en
Inventor
博人 川上
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP52007019A priority Critical patent/JPS6010594B2/en
Publication of JPS5392100A publication Critical patent/JPS5392100A/en
Publication of JPS6010594B2 publication Critical patent/JPS6010594B2/en
Expired legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Control Of Turbines (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)

Description

【発明の詳細な説明】 本発明は原子力発電プラントに係り、特にタービントリ
ッブや原子炉スクラム等の事故後においても崩壊熱を除
去するために必要な給水流軍を確保し得るようにした原
子力発電プラントに関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear power plant, and in particular to a nuclear power plant that is capable of securing the feed water flow necessary to remove decay heat even after an accident such as a turbine trib or reactor scram. Regarding power plants.

・一般に、この種プラントでは、中間熱交換
器等に給水を行なう主給水ポンプとして、小型では電動
駆動のものが採用され、大型になると効率を向上するた
め蒸気駆動の復水タービンが採用されている。
・In general, in this type of plant, an electric-driven main water pump is used to supply water to intermediate heat exchangers, etc. for small-sized plants, and a steam-driven condensing turbine is used for larger plants to improve efficiency. There is.

上記蒸気駆動の復水タービンによる給水ポンプは、高出
力運転時には高圧タービンの排気蒸気をその蒸気源とし
て使用し、低出力運転時には高圧タービンの主塞止弁の
上流側の蒸気に切換えその生蒸気によって主給水ポンプ
駆動タービンを駆動する。これらの給水ポンプはタービ
ントリップと同時にトリツプするように構成されている
The water pump using the steam-driven condensing turbine described above uses the exhaust steam of the high-pressure turbine as its steam source during high-output operation, and switches to the steam upstream of the main shutoff valve of the high-pressure turbine during low-output operation, and uses that live steam. The main water pump drives the turbine. These water pumps are configured to trip at the same time as the turbine trips.

一方、原子力発電プラントにあっては〜原子炉スクラム
、タービントリップ或は電源喪失事故のような時でも、
連続して炉心の崩壊熱を除去する必要がある。
On the other hand, in a nuclear power plant, even in the event of a reactor scram, turbine trip, or power loss accident,
It is necessary to continuously remove the decay heat from the core.

特に高速炉のように1次冷却系、2次冷却系のように中
間サイクルを有する場合には、その間の保有熱も断続し
て際熱する必要がある。しかるに、上記プラントにおい
ては、第2図に示すように、亀勤駆動の給水ポンプでは
電源喪失とともに急激に給水が減少し、起動用給水ポン
プが非常用電源で起動されるまでの間給水がしや断され
る。
In particular, when a fast reactor has intermediate cycles such as a primary cooling system and a secondary cooling system, it is necessary to intermittently heat up the retained heat between them. However, in the above-mentioned plant, as shown in Figure 2, the water supply of the turtle-driven water pump rapidly decreases with the loss of power, and the water supply is interrupted until the start-up water pump is started with the emergency power supply. or be cut off.

また蒸気タービン駆動の給水ポンプでは、タービントリ
ップあるいは主塞止弁閉鎖と同時に生蒸気に切換えられ
て運転されるが、追従性が悪いため一時給水が急激に減
少するとともに安定するまでに長時間を要する。したが
って、その間原子炉側に必要な給水を送水することがで
きず、原子炉における崩壊熱を安全かつ安定した状態で
除去することができない等の不都合があった。本発明は
このような点に鑑み、タービントリツプ、原子炉スクラ
ム等の事故時においても、炉心の崩壊熱を除去するため
に必要な給水流量を確保し得るようににした原子力発電
プラントを提供することを目的とする。
In addition, steam turbine-driven water pumps are operated by switching to live steam at the same time as the turbine trips or the main shutoff valve closes, but due to poor follow-up, the water supply decreases rapidly at one point and takes a long time to stabilize. It takes. Therefore, during this period, necessary water cannot be supplied to the reactor side, resulting in inconveniences such as the inability to safely and stably remove decay heat in the reactor. In view of these points, the present invention provides a nuclear power plant that can secure the necessary water supply flow rate to remove decay heat from the reactor core even in the event of an accident such as a turbine trip or reactor scram. The purpose is to

以下、添付図面を参照して本発明の一実施例について説
明する。
Hereinafter, one embodiment of the present invention will be described with reference to the accompanying drawings.

第1図は本発明の原子力プラントの概略系統図であり、
原子炉1で加熱された冷煤は中間熱交換器2において2
次媒体と熱交換し、さらに1次主循環ポンプ3によって
原子炉1へと循環せしめられる。
FIG. 1 is a schematic system diagram of the nuclear power plant of the present invention,
The cold soot heated in the reactor 1 is transferred to the intermediate heat exchanger 2.
It exchanges heat with the next medium and is further circulated to the reactor 1 by the primary main circulation pump 3.

また、中間熱交換器2によって加熱された2次媒体は過
熱器4および再熱器5に送られ、さらに蒸発器6を通り
2次主循環ポンプ7により中間熱交換器2へと循環され
る。
Further, the secondary medium heated by the intermediate heat exchanger 2 is sent to the superheater 4 and the reheater 5, and further passed through the evaporator 6 and circulated to the intermediate heat exchanger 2 by the secondary main circulation pump 7. .

一方、蒸発器6において上記2次媒体と熱交換して加熱
発生せしめられた蒸気は、気水分磁器8に送られ気水分
離せしめられL過熱器4および主塞止弁9を経て高圧タ
ービン10‘こ供給される。
On the other hand, the steam heated and generated by exchanging heat with the secondary medium in the evaporator 6 is sent to the steam/water porcelain 8 where it is separated from steam and water, passes through the L superheater 4 and the main blocking valve 9, and is then sent to the high pressure turbine 10. 'This will be supplied.

高圧タービン10で仕事を行なった蒸気は再熱器5に送
され、さりこインターセプト弁11を経て中圧タービン
12および低圧ターブン13に順次供給され、それぞれ
中圧タービン12および低圧タービン13で仕事をした
後復水器14で復水される。上記復水器14で復水され
た復水は、復水ポンプ15により低圧給水加熱器16を
経て脱気器17に送られ、さらに給水ポンプ181こよ
り高圧給水加熱器19を経て再び蒸発器6へと循環せし
められる。
The steam that has performed work in the high-pressure turbine 10 is sent to the reheater 5, and is sequentially supplied to the intermediate-pressure turbine 12 and the low-pressure turbine 13 through the saiko intercept valve 11, where it performs work in the intermediate-pressure turbine 12 and the low-pressure turbine 13, respectively. After that, the water is condensed in the condenser 14. The condensate condensed in the condenser 14 is sent to the deaerator 17 via the low-pressure feed water heater 16 by the condensate pump 15, and is then sent to the deaerator 17 via the feed water pump 181, the high-pressure feed water heater 19, and again to the evaporator 6. It is circulated to.

上記給水ポンプ18は互いに並列に接続された起動用給
水ポンプ18aおよび主給水ポンプ18bからなってお
り、起動用給水ポンプ18aは電動機(図示せず)によ
て駆動され、また給水ポンプ18bは前記主塞止弁9よ
り上流側から分岐導出された蒸気によって作動される主
給水ポンプ駆動タービン20iこよって駆動されるよう
に構成され、またその主給水ポンプ駆動タービン20か
らの排気は前記復水器亀4で復水せしめられる。
The water supply pump 18 is composed of a starting water pump 18a and a main water pump 18b which are connected in parallel to each other.The starting water pump 18a is driven by an electric motor (not shown), and the water pump 18b is driven by an electric motor (not shown). It is configured to be driven by a main water pump driving turbine 20i which is operated by steam branched out from the upstream side of the main blocking valve 9, and the exhaust from the main water pump driving turbine 20 is connected to the condenser. It is made to condense in Kame 4.

他方、復水器14の一側上方部には非常用冷却水槽21
が配設されており、循環水ポンプ22により上記復水器
14に冷却水を供給する冷却水供給導管23からの分岐
管24が、ポンプ25を介して上記非常用冷却水槽2川
こ連接され「通常運転時にはポンプ25によって微少流
量の冷却水を供聯合して、非常用冷却水槽2亀を満水状
態に保持している。また、上記非常用冷却水槽21は弁
26を介して前記復水器14への入口部に接続されてお
り「循環水ポンプ22のトリップ時に非常用冷却水槽2
1内の冷却水を前記復水器14に供V給することができ
るようにしてある。なお「図中符号27‘まフラッシュ
タンク28はフロータンク、29は大気放出弁である。
On the other hand, an emergency cooling water tank 21 is located above one side of the condenser 14.
A branch pipe 24 from a cooling water supply conduit 23 that supplies cooling water to the condenser 14 by a circulating water pump 22 is connected to the two emergency cooling water tanks via a pump 25. During normal operation, a small flow of cooling water is supplied by the pump 25 to keep the emergency cooling water tank 2 full of water. The emergency cooling water tank 2 is connected to the inlet of the water tank 14 and
1 can be supplied to the condenser 14. In the figure, the flash tank 28 with reference numeral 27' is a flow tank, and the reference numeral 29 is an atmosphere release valve.

しかして、原子炉スクラム、タービントリツプ、或は電
源喪失事故等が発生すると、大気放出弁29が開かれ過
熱器4を出た蒸気は大気中に放出される。
When a nuclear reactor scram, turbine trip, power loss accident, etc. occurs, the atmosphere release valve 29 is opened and the steam exiting the superheater 4 is released into the atmosphere.

一方、鰭濠喪失時を含め上記事故発生と同時に、起動用
給水ポンプ亀8aが非常用電源に接続され起動される。
しかし、上記起動用給水ポンプ18aが立上るまでには
約3町砂〜1分位の時間がかかるので、その間過熱器4
を出た高圧蒸気の一部によって作動される主給水ポンプ
駆動タービン20‘こよる主給水ポンプ18bの駆動が
続けられ、脱気器17の貯水を水源として利用して、蒸
気器6への給水が行なわれ、2次袷煤等の所要冷却が行
なわれる。そして、過熱器4が隔離された後は、上記蒸
発器6で発生した蒸気は気水分機器8「 フラッシュタ
ンク27を経てブロータンク28から大気中に放出され
る。一方、電源喪失等により循環水ポンプ22がトリツ
プしたような場合には、復水器14をそのま)使用する
ことはできないが、このときには弁26が開放され、非
常用冷却水槽21からの冷却水が復水器14に供聯合さ
れる。
On the other hand, at the same time as the above-mentioned accident occurs, including the loss of the fin moat, the starting water supply pump turtle 8a is connected to the emergency power source and started.
However, it takes about 3 minutes to 1 minute for the start-up water pump 18a to start up, so during that time the superheater 4
The main feed water pump 18b continues to be driven by the main feed water pump driving turbine 20', which is operated by a portion of the high pressure steam that has exited the steam generator, and the water stored in the deaerator 17 is used as a water source to supply water to the steamer 6. is carried out, and the required cooling of the secondary soot, etc. is carried out. After the superheater 4 is isolated, the steam generated in the evaporator 6 is released into the atmosphere from the blow tank 28 through the flash tank 27 of the steam equipment 8. If the pump 22 trips, the condenser 14 cannot be used as is, but in this case the valve 26 is opened and cooling water from the emergency cooling water tank 21 is supplied to the condenser 14. be combined.

したがって、前記起動用給水ポンプが起動され立上るま
での間、十分主給水ポンプ駆動タービンの運転を継続す
ることができ〜必要な給水を行なうことができる。
Therefore, the operation of the main water pump driving turbine can be sufficiently continued until the start-up water pump is started and started up, and necessary water can be supplied.

このように、本発明において主給水ポンプ駆動タービン
を常に主蜜止弁の上流側からの生蒸気によって作動せし
めるようにしたので、第2図において実線で示すように
L事故発生時における給水流量の変化をなめらかに変化
せしめることができ、しかも事故時の給水を確保し原子
炉側に必要な給水を送水することができる。
In this way, in the present invention, the main feedwater pump drive turbine is always operated by live steam from the upstream side of the main stop valve, so the feedwater flow rate at the time of the L accident occurs, as shown by the solid line in Figure 2. Changes can be made smoothly, and water supply can be ensured in the event of an accident, and the necessary water supply can be sent to the reactor side.

しかも本発明においては復水器に非常用冷却水槽を併設
しているので、電源喪失等により復水器用循環ポンプが
トリップしたような場合でも、非常用冷却水槽からの冷
却水が復水器に供給され、主給水ポンプ駆動タービンの
運転を継続できる。したがって、原子炉側に生じる熱過
渡変化を小さく抑えることができ、原子炉を安全かつ安
定した状態で停止させることができ、機器の構造設計条
件をやわらげることができる等の効果を奏する。図面の
簡単な説覇 第亀図は本発明の原子力プラントの概略系統図、第2図
は給水流量の時間変化の比較を示す線図である。
Moreover, in the present invention, since an emergency cooling water tank is attached to the condenser, even if the condenser circulation pump trips due to power loss, etc., cooling water from the emergency cooling water tank can be supplied to the condenser. supply, allowing the main feed water pump drive turbine to continue operating. Therefore, thermal transient changes occurring on the reactor side can be suppressed to a small level, the reactor can be stopped in a safe and stable state, and structural design conditions for equipment can be relaxed. A simple illustration of the drawings: Figure 1 is a schematic system diagram of the nuclear power plant of the present invention, and Figure 2 is a diagram showing a comparison of changes in water supply flow rate over time.

6・・・蒸発器「 9…主菱止弁、亀年・・・復水器、
17・・・脱気器、18a…起動用給水ポンプ、18b
…主給水ポンプ、20・・・主給水ポンプ駆動タービン
、21・・・非常用冷却水槽。
6...Evaporator 9...Main stop valve, Kamenen...Condenser,
17... Deaerator, 18a... Starting water supply pump, 18b
...Main water supply pump, 20...Main water supply pump drive turbine, 21...Emergency cooling water tank.

多Z囚 多そ囚Multi-Z prisoner many prisoners

Claims (1)

【特許請求の範囲】[Claims] 1 主給水ポンプ駆動用タービンを、常時タービン主塞
止弁の上流側からとり入れる生蒸気によって駆動される
復水タービンとするとともに、その復水器には非常用冷
却水槽を併設したことを特徴とする、原子力発電プラン
ト。
1. The turbine for driving the main water supply pump is a condensing turbine driven by live steam constantly taken in from the upstream side of the turbine main blocking valve, and the condenser is equipped with an emergency cooling water tank. A nuclear power plant.
JP52007019A 1977-01-25 1977-01-25 nuclear power plant Expired JPS6010594B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP52007019A JPS6010594B2 (en) 1977-01-25 1977-01-25 nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP52007019A JPS6010594B2 (en) 1977-01-25 1977-01-25 nuclear power plant

Publications (2)

Publication Number Publication Date
JPS5392100A JPS5392100A (en) 1978-08-12
JPS6010594B2 true JPS6010594B2 (en) 1985-03-18

Family

ID=11654316

Family Applications (1)

Application Number Title Priority Date Filing Date
JP52007019A Expired JPS6010594B2 (en) 1977-01-25 1977-01-25 nuclear power plant

Country Status (1)

Country Link
JP (1) JPS6010594B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2487563A1 (en) * 1980-07-25 1982-01-29 Framatome Sa METHOD AND DEVICE FOR COOLING EMERGENCY RESPONSE OF A NUCLEAR REACTOR
US4654190A (en) * 1984-04-05 1987-03-31 Westinghouse Electric Corp. Emergency feedwater system for steam generators of a nuclear power plant

Also Published As

Publication number Publication date
JPS5392100A (en) 1978-08-12

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